Patent · US Active

Apparatus and method for limiting and analyzing stress corrosion cracking in pressurized water reactors

US9280688B2 · kind B2 · utility

1Cited by
15References
10Claims
0Family size

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Inventors

Key dates

Filing dateJun 28, 2013
Grant dateMar 8, 2016
Priority date
Expiry dateJun 28, 2033

Classification

  • Technology area (CPC Y)Emerging Cross-Sectional Technologies
  • CPC primaryY02E30/30
  • WIPO fieldEngines, pumps, turbines
  • WIPO sectorMechanical engineering

Abstract

A method to assess and predict pressurized water stress corrosion cracking in operational nuclear power plants and the effect of adding zinc compounds into a reactor coolant system of the nuclear power plant.

Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.